|
---|
Category:ARCHIVE RECORDS
MONTHYEARML20116A0341996-07-17017 July 1996 Rev 0 to Temp Vs Distance Profile for 10 RHR Line Containing Stagnant Water ML20058Q4061993-08-30030 August 1993 Package Consisting of Employee Concerns Programs ML20128G9491993-01-22022 January 1993 Calculation of Weights Due to Fire Protection Matl ML20128G9551992-12-29029 December 1992 Design Validation of Conduits W/Thermolag ML20128G9861992-10-0202 October 1992 Ampacity of Power Cable Wrapped W/330-660 Installed as Free Air Drop ML20105A7981992-08-14014 August 1992 Rev 0 to Calculation of Thermal Response for Sprinkler & Raceway Supports ML20101G0471992-06-17017 June 1992 Rev 3 to Calculation 2-FP-0085 Raceway & Firezone R Cable Supports Analysis ML20115B6851992-03-0202 March 1992 Rev 0 to 2-NP-GENX-544, Reconciliation of Local Stress Evaluation Using ME215 Analysis ML20104B4001992-02-13013 February 1992 Rev 1 to Calculation RXE-TA-CP1/0-027, Undervoltage/ Underfrequency Reactor Trip Setpoints ML20127H2091991-11-12012 November 1991 Calculation 2-NP-GENX-551, Evaluation of NUREG-0797 Suppl 1A (Sser 14) App a Sections 12.1 & 12.2 ML20082U5851991-05-0808 May 1991 Liner Attachment Welds Serviceability ML20055E2881990-03-12012 March 1990 Package Consisting of Event Notification Worksheet Re 900312 Inadvertent Safety Injection from Single Train.No Equipment Malfunction/Failure Noted ML20072A8471990-01-23023 January 1990 Rev 2 to Calculation 071, Review Statement for Safety Related Calculations ML20042D3711989-09-28028 September 1989 Audit Rept ATP-89-146S, Scaling Calculations, on 890821-0928 ML20247G4111989-03-31031 March 1989 Transit Time Flow Meter Calculations ML20151T3841988-08-0101 August 1988 Protocol Between OSP & NRR for Technical Review of Comanche Peak Fsar ML20151K5841988-04-18018 April 1988 Page from Draft Rept on Plant Safeteam Activity & Ofc of Investigations Review IR 05000445/19820141988-03-11011 March 1988 Draft of Insp Rept 50-445/82-14 Originally Withheld from FOIA-84-210 Response & Typing Cover Sheets or Transmittal Pages of Documents Withheld from FOIA-86-181 Response ML20148F8201988-01-21021 January 1988 Rev 0 to Investigation of SIF for Weld Shrinkage ML20148F8631988-01-21021 January 1988 Rev 1 to Parallel Snubbers ML20148F2151987-11-19019 November 1987 Rev 0 to Potential Binding of Lugs in Axial Supports ML20237K9771987-08-19019 August 1987 Press Release 87-115 Informing of NRC Release of Documents Re Investigation of NRC Actions Involving Plant Under Const. Portions of Documents Deleted for Personal Privacy Reasons or Prospective Personnel Matters ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20148F2521987-05-22022 May 1987 Rev 0 to Evaluation of Fluid Transient Cutoff Forces & Development of Screening Criteria for Piping Sys ML20237K0381987-05-14014 May 1987 Record of 870514 Telcon W/S&W & Util Re Insp Requirements for Pipe Supports (Ref Item 4,SWEC NA-1140 Rept) ML20237K0201987-05-13013 May 1987 Record of 870513 Telcon W/S&W & Util Re Insp Requirements for Pipe Supports for Plant.S&W Does Not Consider Insp of Designs to Be Warranted ML20236M4011987-04-17017 April 1987 Package Consisting of 870417 Request for Premium Cost Mail Svc & Unsigned & Undated Ltr to Util Forwarding Draft Insp Repts 50-445/87-02 & 50-446/87-02 & Notice of Deviation ML20128G9681987-02-24024 February 1987 Cable Ampacity Derating Factors for Conduits Boxed in W/ Thermolag (TSI Product) ML20236L9091987-02-19019 February 1987 Rev 1 to CT-1-137-701-S25R, Pipe Support Calculation ML20236N4981987-02-0202 February 1987 Package Consisting of Comanche Peak Steam Electric Station Design Change Authorizations & Evaluation Summaries ML20207D7231986-12-23023 December 1986 Pipe Support Calculation:General Calculation for Richmond Insert/Tube Steel Connections Design Mods ML20207D7481986-12-23023 December 1986 Generic Calculation:Evaluation of Npsi Rear Brackets, Dimension for Design Calculation IA-86-386, Package Consisting of Potential Violations Not Included in Proposed Enforcement Package & Violations of Little Safety Significance Not Included in Proposed Enforcement Package1986-12-16016 December 1986 Package Consisting of Potential Violations Not Included in Proposed Enforcement Package & Violations of Little Safety Significance Not Included in Proposed Enforcement Package ML20211P4701986-12-16016 December 1986 Package Consisting of Potential Violations Not Included in Proposed Enforcement Package & Violations of Little Safety Significance Not Included in Proposed Enforcement Package IA-85-799, Partially Withheld Package of Info Re Plant Investigation, Including Draft NRC Ltr to Aslb,Partial Transcript & Handwritten Notes1986-12-0101 December 1986 Partially Withheld Package of Info Re Plant Investigation, Including Draft NRC Ltr to Aslb,Partial Transcript & Handwritten Notes ML20214R3351986-12-0101 December 1986 Partially Withheld Package of Info Re Plant Investigation, Including Draft NRC Ltr to Aslb,Partial Transcript & Handwritten Notes ML20235S1101986-11-15015 November 1986 Package of Documents Re Nomination & Authorization for Cash Awards to NRC Personnel Involved W/Insp Efforts Re Implementation of Util Comanche Peak Response Team Program IA-87-528, Package of Documents Re Nomination & Authorization for Cash Awards to NRC Personnel Involved W/Insp Efforts Re Implementation of Util Comanche Peak Response Team Program1986-11-15015 November 1986 Package of Documents Re Nomination & Authorization for Cash Awards to NRC Personnel Involved W/Insp Efforts Re Implementation of Util Comanche Peak Response Team Program ML20210E5991986-11-0707 November 1986 Rev 2 to Calculation 020-040-M19, Clip Stiffness Production Value ML20210E6811986-10-31031 October 1986 Rev 4 to Calculation M-03, Cable Tray Properties ML20236L8891986-10-31031 October 1986 Rev 1 to CT-1-137-702-S25R, Pipe Support Calculation. Supporting Documentation Encl ML20210E5221986-10-15015 October 1986 Rev 2 to Calculation M-10, Cable Tray - Clip Angle Stiffness ML20210E5751986-10-10010 October 1986 Rev 2 to Calculation M-12, Qualification Procedures for Cable Tray Support Evaluation ML20148F4591986-09-16016 September 1986 Rev 0 to Fatigue Cycle Determination for Pipe Supports ML20148F4921986-09-10010 September 1986 Rev 2 to Documentation of Use of Low Strength A563 Grade a Double Nuts on High Strength SA 193 Grade B-7th D Rod for Richmond Insert Bolt Connection ML20210E6261986-08-31031 August 1986 Rev 0 to Calculation M-28, Justification of Clip Modeling Procedure ML20148F3351986-08-28028 August 1986 Rev 2 to Development of Method for Evaluating Local Stress in Pipe Support Members ML20210E4611986-08-25025 August 1986 Rev 3 to Calculation M-25, Base Plate Prying Action Factors ML20236L9371986-07-31031 July 1986 Rev 1 to Calculation CT-1-032, Texas Util Generating Co Comanche Peak Steam Electric Station Containment Spray Sys 15454-NP(H) ML20211K2971986-06-11011 June 1986 Partially Withheld Package of 850711 & 860611 Lists of Allegations on Comanche Peak 1996-07-17
[Table view] Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20116A0341996-07-17017 July 1996 Rev 0 to Temp Vs Distance Profile for 10 RHR Line Containing Stagnant Water ML20128G9491993-01-22022 January 1993 Calculation of Weights Due to Fire Protection Matl ML20128G9551992-12-29029 December 1992 Design Validation of Conduits W/Thermolag ML20128G9861992-10-0202 October 1992 Ampacity of Power Cable Wrapped W/330-660 Installed as Free Air Drop ML20105A7981992-08-14014 August 1992 Rev 0 to Calculation of Thermal Response for Sprinkler & Raceway Supports ML20101G0471992-06-17017 June 1992 Rev 3 to Calculation 2-FP-0085 Raceway & Firezone R Cable Supports Analysis ML20115B6851992-03-0202 March 1992 Rev 0 to 2-NP-GENX-544, Reconciliation of Local Stress Evaluation Using ME215 Analysis ML20104B4001992-02-13013 February 1992 Rev 1 to Calculation RXE-TA-CP1/0-027, Undervoltage/ Underfrequency Reactor Trip Setpoints ML20127H2091991-11-12012 November 1991 Calculation 2-NP-GENX-551, Evaluation of NUREG-0797 Suppl 1A (Sser 14) App a Sections 12.1 & 12.2 ML20082U5851991-05-0808 May 1991 Liner Attachment Welds Serviceability ML20072A8471990-01-23023 January 1990 Rev 2 to Calculation 071, Review Statement for Safety Related Calculations ML20247G4111989-03-31031 March 1989 Transit Time Flow Meter Calculations ML20148F8201988-01-21021 January 1988 Rev 0 to Investigation of SIF for Weld Shrinkage ML20148F8631988-01-21021 January 1988 Rev 1 to Parallel Snubbers ML20148F2151987-11-19019 November 1987 Rev 0 to Potential Binding of Lugs in Axial Supports ML20148F2521987-05-22022 May 1987 Rev 0 to Evaluation of Fluid Transient Cutoff Forces & Development of Screening Criteria for Piping Sys ML20128G9681987-02-24024 February 1987 Cable Ampacity Derating Factors for Conduits Boxed in W/ Thermolag (TSI Product) ML20236L9091987-02-19019 February 1987 Rev 1 to CT-1-137-701-S25R, Pipe Support Calculation ML20207D7481986-12-23023 December 1986 Generic Calculation:Evaluation of Npsi Rear Brackets, Dimension for Design Calculation ML20207D7231986-12-23023 December 1986 Pipe Support Calculation:General Calculation for Richmond Insert/Tube Steel Connections Design Mods ML20210E5991986-11-0707 November 1986 Rev 2 to Calculation 020-040-M19, Clip Stiffness Production Value ML20236L8891986-10-31031 October 1986 Rev 1 to CT-1-137-702-S25R, Pipe Support Calculation. Supporting Documentation Encl ML20210E6811986-10-31031 October 1986 Rev 4 to Calculation M-03, Cable Tray Properties ML20210E5221986-10-15015 October 1986 Rev 2 to Calculation M-10, Cable Tray - Clip Angle Stiffness ML20210E5751986-10-10010 October 1986 Rev 2 to Calculation M-12, Qualification Procedures for Cable Tray Support Evaluation ML20148F4591986-09-16016 September 1986 Rev 0 to Fatigue Cycle Determination for Pipe Supports ML20148F4921986-09-10010 September 1986 Rev 2 to Documentation of Use of Low Strength A563 Grade a Double Nuts on High Strength SA 193 Grade B-7th D Rod for Richmond Insert Bolt Connection ML20210E6261986-08-31031 August 1986 Rev 0 to Calculation M-28, Justification of Clip Modeling Procedure ML20148F3351986-08-28028 August 1986 Rev 2 to Development of Method for Evaluating Local Stress in Pipe Support Members ML20210E4611986-08-25025 August 1986 Rev 3 to Calculation M-25, Base Plate Prying Action Factors ML20236L9371986-07-31031 July 1986 Rev 1 to Calculation CT-1-032, Texas Util Generating Co Comanche Peak Steam Electric Station Containment Spray Sys 15454-NP(H) ML20210E6171986-05-29029 May 1986 Rev 0 to Calculation M-27, Thermal Load Position Paper ML20210E7031986-05-27027 May 1986 Rev 0 to Calculation M-39, Siderail Extension Study ML20148F1131986-04-0404 April 1986 Rev 0 to Justification of Design Load for Struts/Snubbers & Lugs Used in Conjunction W/Riser Clamp ML20210E4911986-03-21021 March 1986 Rev 1 to Calculation M-04, Base Angle Stiffness ML20148F7181982-04-21021 April 1982 Rev 1 to Stress Intensification Factors for Lateral Branches Fabricated from `Welded-In' Piping to Be Used in ASME Class 3 & ANSI B31.1 Pipe Stress Analysis 1996-07-17
[Table view] |
Text
_ - _ _ _ - _ _
WESTINGHOUSE CLASS 3 i
WCAP-12229 i
s TRANSITTIMEFLOWMETER(TTFM)
CALCULATIONS
\
l March, 1989 C. R. Tuley 8904040219 8?/5331 ~'
h) PDR ADOCK 05000445 A PDC n.... ,,_
WESTINGHOUSE ELECTRIC CORPORATION Power Systems i P. O. Box 355 l
Pittsburgh, Pennsylvania 15230 f
l l
} Per an NRC requirement specified at a Texas Utilities / Westinghouse /NRC l
meeting on 10/11/84, Westinghouse has included an "NRC conservatism factor" 4 in the determination of the minimum RCS Flow that Comanche Peak must verify at the beginning of a cycle. There was some concern expressed by the NRC staff concerning the magnitude of the uncertainty of the Azimuthal Velocity Profile for the Transit Time Flow Meter (TTFM). Westinghouse includes an allowance of [
)+a,c. The NRC specified that a value of [ -]+a,c be used as the accuracy of the TTFM on a single loop basis. Westinghouse calculates that the accuracy of the TTFM is [ ]+a,c on a single loop basis. Using the NRC specified value, and assuming that the conservatism factor is treated as a random, j loop independent parameter allows the determination of the magnitude of the "NRC conservatism factor". This value is:
x.[ .]+a,c
.[ )+a,c, The value for X is then included with the random uncertainties associated with the use of the TTFM. These are:
Fluid Flow - -
+a,c Radial Velocity Profile -
Cross Flow -
Mechanical Detector Spacing and Detector /Collimator Angle - 1 Pipe Internal Cross Sectional Area -
Data Collection Statistics -
Data Reduction -
Using the Square Root of the Sum of the Squares (SRSS) technique, these
, uncertainties total [ ]+a,c. The systematic uncertainty for l the Azimuthal Velocity Profile is as noted above.
I j
l l
The random and systematic components of the TTFM uncertainty are utilized 4 twice in the calculation of the precision RCS Flow measurement uncertainty. The first utilization is in the determination of [
]+a,c. The second time they are used is in the
[ ]+a,c. In both instances, ,
the NRC specified conservatism factor is an integral part of the TTFM random uncertainty. In fact, an investigation of the uncertainties listed on the previous page will result in the conclusion that the NRC specified l conservatism factor is the largest component of the SRSS of the TTFM random uncertainties. Inclusion of the conservatism factor increases the SRSS of the TTFM random uncertainties by [ ]+a,c, The precision RCS Flow measurement uncertainty is then combined with the uncertainty associated with the use of the Cold Leg Elbow Taps. The j uncertainty for use of one Elbow Tap per loop, indicated via the plant process computer is comb ued (via SRSS) with the precision RCS Flow measurement uncertainty. This combination forms the total RCS Flow measurement uncertainty.
The difference between the total RCS Flow measurement uncertainty, with and without the conservatism factor, is significant. With the conservatism factor, the total uncertainty is [ ]+a,c. Without the conservatism factor, the total uncertainty is [ ]+a,c. The value with the conservatism factor is used to determine the minimum measured flow at the beginning of the cycle, i.e., the plant must measure X gpm where X includes an allowance of [. ]+a,c for measurement uncertainty.
Based on the above discussion, Westinghouse believes that the NRC specified conservatism factor has been appropriately determined and included in the
, calculation of the uncertainty for the TTFM and subsequently the precision
,' RCS Flow measurement uncertainty and the total RCS Flow measurement
uncertainty. In addition, this conservatively determined uncertainty has
.- . been appropriately specified in the Comanche Peak Technical Specifications to assure that the minimum flow present in the plant exceeds the analysis
.'4 assumptions.
4 i
i O
h e
o i 4
e
._ __- _ - _ - _ - - - _ _ ,